U.S. patent number 3,668,070 [Application Number 04/823,681] was granted by the patent office on 1972-06-06 for nuclear reactor with heat pipes for heat extraction.
This patent grant is currently assigned to European Atomic Energy Community (Euratom). Invention is credited to Peter Fiebelmann, Helmut Neu.
United States Patent |
3,668,070 |
Fiebelmann , et al. |
June 6, 1972 |
NUCLEAR REACTOR WITH HEAT PIPES FOR HEAT EXTRACTION
Abstract
A nuclear reactor with a heat extraction system comprising two
groups of heat pipes which extend through the reactor core and
which deliver heat to heat sinks disposed outside the core. All
pipes of one group being parallel, the two groups are arranged in a
mutual right angle relation and they intersect each other.
Inventors: |
Fiebelmann; Peter (Besozzo,
IT), Neu; Helmut (Travedona, IT) |
Assignee: |
European Atomic Energy Community
(Euratom) (Brussels, BE)
|
Family
ID: |
5697943 |
Appl.
No.: |
04/823,681 |
Filed: |
May 12, 1969 |
Foreign Application Priority Data
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|
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May 21, 1968 [DT] |
|
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P 17 64 347.9 |
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Current U.S.
Class: |
376/367;
165/104.21; 376/288; 976/DIG.188; 116/40; 310/306; 376/321 |
Current CPC
Class: |
G21C
15/02 (20130101); Y02E 30/30 (20130101); Y02E
30/40 (20130101) |
Current International
Class: |
G21C
15/02 (20060101); G21C 15/00 (20060101); G21k
014/00 () |
Field of
Search: |
;176/39-43 ;310/4
;165/105 |
References Cited
[Referenced By]
U.S. Patent Documents
Primary Examiner: Epstein; Reuben
Claims
1. A nuclear reactor with a heat extraction system comprising a
plurality of hermetically sealed heat pipes, which extend through
the core zone and are mechanically held by means of thermal and
electrical insulators in the zone of a reflector surrounding the
core zone, the heat pipes being subdivided into two groups with
axial orientations of the heat pipes of one group disposed at an
angle relative to the heat pipes of the other
2. A nuclear reactor according to claim 1, in which the nuclear
fuel comprises substantially cube-shaped elements of which each is
provided with two bores containing heat pipes disposed orthogonally
to each other and parallel to two of the principal axes of the cube
the elements in the core being stacked with the bores of the
elements in alignment with each
3. A nuclear reactor according to claim 1, in which the diameters
of the reactor core bores for the heat pipes are substantially
larger than the external diameters of the heat pipes, so that there
is clearance between the heat pipes and the walls of the bores in
which they are received.
Description
The invention relates to a nuclear reactor with a heat extraction
system comprising a plurality of hermetically sealed heat pipes,
one end of these heat pipes extending into the reactor core.
Proposals have recently been made for the extraction of reaction
heat from a reactor core (see for example French Patent
Specification No. 1,455,672) in which the conventional integral
cooling system with coolant flowing through a plurality of ducts of
the reactor core was replaced by a plurality of cooling circuits
disposed in parallel to each other and being completely independent
of each other. Each cooling circuit comprises a hermetically
sealed, so-called heat pipe, partially filled with a thermal
transfer medium and adapted to extend into the core to dissipate
the heat, with very small losses, to a heat sink disposed in the
region of a part of the pipe which extends from the core. The heat
sink is preferably constructed as a direct energy converter (for
example in accordance with the thermionic principle).
One of the difficulties which militates against the practical
application of the aforementioned heat pipe cooling system is the
danger which flows from a possible failure of a single heat pipe.
An excessive temperature rise would then occur in the zone
surrounding the defective heat pipe, the adjacent heat pipes being
unable to absorb said temperature rise so that the fuel elements
could melt. In view of the very high normal operating temperatures
of 1,500.degree. C and more required for thermionic converters it
is not possible reliably to prevent the failure of a heat pipe, for
example due to corrosion of the pipe walls. In parallel heat pipe
systems there is no substantial thermal contact between adjacent
heat pipes, particularly in thermal reactors in which each heat
pipe is provided with its own fuel shell and a moderator of low
operating temperature is disposed between fuel elements. Failure of
a heat pipe in such cases will inevitably be followed by melting of
the fuel.
The catastrophic consequences described hereinabove of the failure
of a single heat pipe are avoided or lessened in the reactor
concept according to the invention.
According to the invention the heat pipes are not disposed
throughout in parallel but are subdivided into two groups with
axial orientations of the heat pipes disposed at an angle relative
to each other and the axes of the two groups intersect in the core
zone. Under these conditions not only may two to six heat pipes be
disposed in the immediate neighborhood of any pipe which may become
defective but a substantially larger number of heat pipes may
intersect their cooling area thus ensuring adequate heat
dissipation.
In a preferred embodiment of the invention the reactor core is
constructed of a plurality of substantially cube-shaped fuel
elements each of which is provided with two bores disposed
orthogonally to each other and in parallel to two of its principal
axes, the elements in the core being stacked with the bores of the
elements in alignment with each other so as to accommodate heat
pipes therein. In a preferred embodiment the heat pipes extend
through the entire core zone and are mechanically retained or
supported via thermal and electrical insulators only in the zone of
a reflector which surrounds the core zone. To prevent damage to the
heat pipes due to varying thermal expansion between the core and
the reflector it is advantageous to extend the heat pipes freely
through the core ducts and to allow thermal transfer to take place
by radiation. Such a procedure also offers the advantage of
dispensing with the need for supporting insulators in the core zone
which would have to be exposed to the extremely high temperatures
of the core.
Some specific examples of the invention will now be described with
reference to the accompanying drawings in which:
FIG. 1 is a view of a fuel element,
FIG. 2 is a partially sectioned view of a reactor core;
FIG. 3 is a partially sectioned view of another reactor core.
The cube-shaped fuel element illustrated in FIG. 1 is traversed in
different horizontal planes by two superjacently disposed bores.
The bores are in each case disposed parallel to a cube axis. The
bore diameter is sufficiently large to enable the intended heat
pipes to be inserted therein with clearance. The fuel elements
contain the nuclear fuel which is distributed in a matrix of good
thermal conductivity. For example uranium oxide cement or uranium
carbide, stabilized with ZrC may be employed to this end.
The reactor core according to FIG. 2 is constructed from such
cube-shaped elements. A substantially square stratum of fuel
elements 3 alternates in each case with a stratum comprising
moderator elements 4. The fuel element blocks are disposed
adjacently so that the holes 1 and 2 for the heat pipes 5 are in
alignment. Said heat pipes project from the reactor core and are
mechanically held in the region of a reflector shell 6 which
surrounds the core and are connected to thermionic converters 7.
Thermal shields 8 are provided between the strata of fuel and
moderator elements and the moderator elements are traversed by a
separate cooling system, not shown, in order to maintain a low
temperature of the moderator which may consist for example of flat
discs of metalhydrides. The separate cooling system may be a
conventional circuit or may operate in accordance with the heat
pipe principle. The moderator and heat shields are omitted in the
case of a fast reactor.
If the thermal conductivity of the fuel elements is sufficiently
high, the temperature rise on a defective heat pipe will remain low
because the amount of heat normally dissipated by the defective
heat pipe is uniformly transferred over a plurality of the
aforementioned intersecting heat pipes.
FIG. 3 is a view partly in section of a nuclear reactor which is
provided as an energy source for a space station and incorporates
heat pipes for heat extraction disposed in the intersected manner
according to the invention. The reactor is completely surrounded by
a reflector shell 9 whose temperature is maintained at
approximately 800.degree. C by means of a cooling circuit (cooling
ducts 10). The reactor core itself comprises a plurality of fuel
rods 11 which are disposed in a plurality of superjacent layers,
the axes of the rods in adjacent layers being perpendicular to each
other, as viewed in plan.
A space through which a heat pipe 12 extends is disposed between
each two fuel rods of a layer. The dimensions of the space and of
the heat pipe are selected to avoid that said heat pipe touches the
fuel at any position. Instead, the heat pipe is held in the region
of the reflector 9. The heat pipes traverse the entire core and
their ends 13, distal relative to the cooling zone, are retained in
recesses of the reflector shell by means of a thermal and
electrical insulating stratum 17. The cooling zones of the heat
pipes are disposed outside the reflector and are directly coupled
to thermionic converters 14. Thermal and electrical insulating
strata 17 are also provided where the heat pipes pass through the
reflector. For the sake of completeness reference is also made to
the collector side heat pipes 15 which duct the waste heat losses
from the converters to radiating coolers not shown, reference also
being made to movable reflector elements 16 for controlling the
reactivity.
The principle employed herein for transferring heat from the fuel
to the heat pipes by means of radiation ensures that all supporting
and insulating elements may be disposed in the region of the
relatively cool reflector and that slightly different coefficients
of expansion between the heat pipes or the reflector shell and the
fuel can be absorbed without operational defects. The temperature
of the reactor core with an operating power of for example 500 kW
was fixed at 1,600.degree. C in the present example to enable the
thermionic converters 14 to operate in a favorable power range.
Thermal insulation for the holding means of the heat pipes may
comprise tungsten, which, in the form of sheeting, is coiled around
the heat pipes so that small spacers form insulating spaces between
the individual coils. The electrically insulating stratum of
ceramic material disposed thereabove need then only withstand a
temperature of up to 800.degree. C.
Although disposing the heat pipes in parallel to two principal axes
of the reactor core represents the geometrically simplest solution
of the problem, the invention may also be performed with heat pipes
extending at an angle through the fuel elements and with other
forms of fuel element. The invention, as applied to thermal
reactors in which the fuel is disposed in a moderating matrix or
adjacent to moderator elements, may also be applied to a so-called
fast reactor in which the moderating elements are omitted.
* * * * *